ML20148H919
| ML20148H919 | |
| Person / Time | |
|---|---|
| Site: | 07109122 |
| Issue date: | 11/06/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20148H926 | List: |
| References | |
| NUDOCS 7811150046 | |
| Download: ML20148H919 (6) | |
Text
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Form NRC-618 U.S. NUCLE AR REGULATORY COMMISSION U
CERTIFICATE OF COMPLI ANCE M CF 71 v
For Radioactive Materials Packages 1.(4) Certificate Number 1.(b) Revision No.
1.(c) Packap identification No.
1.(d) Pages No. 1.(e) Total No. Pages i
9122 0
USA /9122/A 1
3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a 173.394,173.395, and 173.396 of the D*partment of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, "Fackaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Tre.nsportation or other applicable regulatory agencies, including the government of any country through or into which the package j
will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application P. O. Box 1866 dated August 14, 1978, as supplemented.
Bellevue, WA 98009
~9 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.:
18-450 (2) Description The packaging is a top-loaded, welded steel encased lead shielded, prismatic cask for LSA materials.
The packaging is 96 inches square and 124 inches high with a cavity 88-1/2 inches square and 99-1/2 inches high.
The sides consist of 1/2 inch of lead between a 1/2-inch outer steel plate and a 1/4-inch inner plate.
The lid and base are 1/2 inch of lead between 1/4-inch steel plates with 4-inch beams, covered with 1/4-inch steel plates, on the outer surfaces.
A 1-1/2-inch steel plate covers the bottom of the cavity. Additional shielding is provided by side plates.
The 72-inch high side plates are 3-1/2 inches thick carbon steel, placed within the cavity.
Packaging side walls are reinforced by 8-inch I-Beams at four places around the outside of the packaging perimeter.
The neoprene gasketed lid is attached by twelve, 1-inch diameter steel eyebolts and nuts.
The maximum gross weight of the package is approximately 61,000 pounds.
7811I5oo 46
Page 2 - Certificate No. 9122 - Revision No. 0 - Docket No. 71-9122 5.
(a) Packaging (continued)
(3) Drawing The packaging is constructed in accordance with Chem-Nuclear Systems, Inc., Drawing No. E-182-201; Sheet No. 1, Rev. H and Sheet No. 2, Rev. G.
(b) Contents (1) Type and form of material Dewatered or solidified waste meeting the requirements of low specific activity radioactive material as defined in 10 CFR 571.4(g), in a secondary container.
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the weight of the contents, secondary container and shoring not exceeding 8,000 pounds.
6.
Shoring shall be placed between the secondary container and the cask cavity to prevent movement during normal conditions of transport.
7.
The. lifting shackles shall be plugged or covered in transit to preclude their use for cask tie-down.
8.
The packaging shall be visually inspected prior to each use to detect significant ttansport damage. Any damage detected is to be appropriately repaired prior to shipment.
9.
The package authorized by this certificate shall be transported on a motor vehicle, railroad car, aircraf t, inland water craft, or hold or deck of a seagoing vessel assigned for the sole use of the licensee.
- 10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
11.
Expiration date: October 31, 1983
Page 3 - Certificate No. 9122 - Revision No. 0 - Docket No. 71-9122 REFERENCES 1
Chem-Nuclear Systems, Inc. application dated August 14, 1978.
Supplements dated:
September 8 and 20 and October 11 and 18,1978.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION h
Charles E. liacDonald, Chief Transportation Branch Division of Fuel Cycle and flaterial Safety
)
NOV 0 61978 Date:
U.S. NUCLEAR REGULATORY COMMISSION TRANSPORTATION BRANCH SAFETY EVALUATION OF CHEM-NUCLEAR SYSTEMS, INC.,
MODEL NO.18-450 PACKAGING, Encl to ltr dtd:
Summary By application dated August 14, 1978, as supplemented, Chem-Nuclear used for shipment of low specific activity material (LSA) packaging to be System, Inc. requested approval for the Model No.18-450 where the total amount of radioactive material is greater than a Type A quantity as defined in 10 CFR 571.4(q).
Based on the statements and representations contained in the application the staff has concluded that the Model No.18-450 packaging, and its contents as described, meat the requirements of 10 CFR Part 71 for Type A packaging.
References Chem-Nuclear System, Inc. application dated August 14, 1978.
Supplements Dated:
September 8 and 20 and October 11 and 18, 1978.
Drawing The packaging is fabricated according to Chem-Nuclear Systems, Inc.,
Drawing No. E-182-201; Sheet No. 1, Rev. H and Sheet No. 2, Rev. G.
Packaging Description The packaging is a top-loaded, welded steel encased lead shielded, prismatic cask for LSA materials.
The packaging is 96 inches square and 124 inches high with a cavity 88-1/2 inches square and 99-1/2 inches high. The sides consist of 1/2 inch of lead between a 1/2-inch outer steel plate and a 1/4-inch inner plate.
The lid and base are 1/2 inch of lead between 1/4-inch steel plates with 4-inch beams, covered with 1/4-inch steel plates, on the outer surfaces. A 1-1/2-inch steel plate covers the bottom of the cavity.
Additional shielding is provided by side plates.
The 72-inch high side plates are 3-1/2 inches thick carbon steel, placed within the cavity.
Packaging side walls are reinforced by 8-inch I-Beams at four places around the outside of the packaging peri-meter. The neoprene gasketed lid is attached by twelve,1-inch diameter steel eyebolts and nuts.
The maximum gross weight of the package is approximately 61,000 pounds.
~
4.
Contents The packaging is designed for the shipment of dewatered and solidified waste within a secondary container. The contents are restricted to low specific' activity radioactive materials as defined in 10 CFR.571.4(g).
The secondary container is secured within the cask cavity using shoring to prevent movement during normal conditions of transport.
The maximum weight of contents, secondary container and shoring shall not exceed 1
8,000 pounds.
j Structural / Thermal Evaluation General Standards - The steel and lead within the package will not significantly interact with the contents in a disposable steel liner.
The lid is bolted to the cask.
No other access to the cavity is provided.
It was demonstrated by analysis that the effectiveness of the package would not be reduced by a 3 g lifting load.
Standard 1-1/4-inch shackles through the four lifting lugs are considered structural parts of the packaging.
For an excessive lifting load,10 CFR 571.31(c)(4), the shackles would fail before any other component.
Therefore, the contain-ment and shielding properties of the packaging would not be impaired.
Structural Standards - The load resistance condition was shown to result in stresses below yield. The external pressure condition would result in a significant deformation in the middle of the lid, however failure would not occur and the gasket should maintain a cavity seal as the deformations at the lid edge are small. Side wall deformation at the lid should not affect the seal.
Normal Conditions of Transport - The packa9.ng is of such construction 4
and the contents so limited that exposure to direct sunlight at 130 F '
in still air would have no detrimental effects because of the nature of the materials being shipped, materials of construction, and the limited heat load (less than 50 watts).
It was determined that the packaging materials would not be adversely affected by the cold temperature environ-ment. Although the vibration condition was not addressed, it is not likely that gross fatigue damage, resulting from the normal transport vibration environment, would occur since the package has been in use since 1973.
In addition, the packaging will be visually inspected prior to each use to detect significant transport damage.
Any damage observed is to be appropriately repaired prior to shipment.
The materials of construction and sealed cavity would preclude damage due to the water spray environment. The package was assessed for a one-foot drop onto the bottom surface. The assessment showed that a lead slump of no more
.than one inch may result and that the lid gasket would maintain its t
-w
i i integrity.
Because of the size and tie-down arrangement, the need for other one-foot drop orientation was not considered necessary.
Missiles which could be thrown at the packaging should have no significant effect on shielding or containment.
The construction of the outer surface of the package, either one, 1/2-inch plate or two,1/4-inch plates, and the lack of any exposed sensitive cavity protrusions allow the staff to conclude that the impact of the penetration cylinder at any point would not significantly alter the packaging effectiveness. The size of the packaging exempts it from the requirements of 10 CFR 571.35 for the corner drop and compression tests.
Hypothetical Accident Conditions - Since the packaging is used for shipment of low specific activity radioactive material on a motor vehicle, railroad car, aircraft, inland watercraft, or hold or deck of a sesgoing vessel assigned for sole use of the license, pursuant to 10 CFR 71.36(a), it need not satisfy the hypothetical accident conditions.
Containment i
The structural / thermal evaluation has demonstrated that containment effcctiveness of the packaging is not significantly reduced as a result l
of normal conditions of transport.
Shielding The lid end lead slump would result in a radiation streaming window just below the lid, however the staff concludes that the one inch lid stop plate and the 1/4-inch lid edge angle is equivalent for radiation attenuation (0.6 to 1.33 mev ganna) to the 1/2-inch lead lost at impact.
Therefore there will be no significant reduction of shielding effective-ness under the normal conditions of transport.
M Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Date:
j